Verification of Historical System Transient Simulations for the RHF Research Reactor
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Institut Laue-Langevin (ILL), Grenoble (France)
The RELAP5/Mod 3.3 [1] reactor transient analysis code was used to perform a verification of the RHF reactor system transients previously simulated with the CATHARE Code. The verification included comparisons of temperature, pressure, flows, etc. where direct code comparisons could be made. This work is a precursor to the simulations that will be performed with the RELAP5 code to evaluate the impact of converting the RHF reactor from Highly Enriched Uranium (HEU) to Low Enriched Uranium (LEU) fuel.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE); USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation (NA-20). Office of Material Management and Minimization (M3)
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1463240
- Report Number(s):
- ANL/RTR/TM-15/5; 143454; TRN: US1901664
- Country of Publication:
- United States
- Language:
- English
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